OOIR: Observatory of International Research

Papers

(The median citation count of Science and Technology of Nuclear Installations is 1. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2022-05-01 to 2026-05-01.)

Article	Citations
Investigation of Oxidation and Counter-Oxidation in a One-Quarter Circular Geometry due to Shadow Corrosion	31
Vacuum Analysis and Experiment of Free‐Electron Laser Oscillator Based on Molflow+ Simulation	15
Effect of Inhomogeneous Mechanical Properties on the Stress-Strain Field at the Crack Tip and Crack Growth Direction in Dissimilar Metal Welded Joints	11
An Information Granulated Based SVM Approach for Anomaly Detection of Main Transformers in Nuclear Power Plants	10
Implications of Innovative Nuclear Technologies on Ghana’s Nuclear Future	9
Cold Atmospheric Plasma Inhibits the Proliferation of CAL-62 Cells through the ROS-Mediated PI3K/Akt/mTOR Signaling Pathway	9
Study on Fuel Rod Melting and Molten Material Migration in Core Channels Based on Particle Method	8
Investigation of Early Corrosion Behavior of Canister Candidate Materials in Oxic Groundwater by the EQCM Method	7
Development of an Integrated Human Error Simulation Model in Nuclear Power Plant Decommissioning Activities	7
Research on Optimization of Roof Shielding Design for Radioactive Waste Temporary Storage Facilities	7
Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library	7
	6
Improvement of the Power Supply Technical Scheme for the Electric Melter System in High‐Level Radioactive Liquid Waste Vitrification	6
The Design and Analysis of Active–Passive Hybrid Vibration Isolation Mounts Applied in Pump	6
Nuclear Waste Management: A Mini Review on Waste Package Characterization Approaches	5
Evaluation of Worker Radiation Exposure during the Kori Unit 1 Steam Generator Dismantling Process	5
Pressure Distribution on the Inner Wall of the Volute Casing of a Centrifugal Pump	4
Optimization of the n / γ Pulse Shape Discrimination Performance of Plastic Scintillator Coupled With SiPM	4
Accident Sequence Precursor Analysis of an Incident in a Japanese Nuclear Power Plant Based on Dynamic Probabilistic Risk Assessment	4
Time‐Series Forecasting of a Typical PWR Undergoing Large Break LOCA	4
Prediction of Crack Propagation Directions in Dissimilar Metal‐Welded Joints Using Phase‐Field Models and Discussion of Its Mechanisms	4
Correction to “Count Loss Evaluation for Accuracy Enhancement of a FPGA‐Based Gamma Spectroscopy”	4
Detecting Unauthorized Movement of Radioactive Material Packages in Transport with an Adam-Optimized BP Neural Network Model	4
ELSMOR European Project: Experimental Results on an Innovative Decay Heat Removal System Based on a Plate-Type Heat Exchanger	4
A Data-Driven Fault Prediction Method for Nuclear Power Systems Based on End-to-End Deep Learning Framework	4

Prediction of Automatic Scram during Abnormal Conditions of Nuclear Power Plants Based on Long Short-Term Memory (LSTM) and Dropout	3
An Improved Steady-State and Transient Analysis of the RSG-GAS Reactor Core under RIA Conditions Using MTR-DYN and EUREKA-2/RR Codes	3
Effect of Chloride Ions on Electrochemical Behavior of Canister Materials	3
Research on Radionuclide Diffusion Mechanism in the Ocean and Emergency Response under Oceanic Radioactive Events	3
Exponential Response Matrix Spectral Nodal Method for the Discrete Ordinates Neutral Particle Transport Model	3
Assessment of Computational Technicalities for 2D/1D Coupling Method and Its Comparison with 3D MOC	3
A Hybrid Method to Predict the Remaining Useful Life of Scroll Wheel of Control Rod Drive Mechanism	3
Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material	3
Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations	3
Enhancing Radiation Shielding with Gadolinium(III) Oxide in Cerium(III) Fluoride‐Doped Silica Borate Glass	3
The Study of Dosimetric Characteristics of the XHA600D Medical Linear Accelerator Based on a Monte Carlo Code	3
	2
Coincidence Summing Factor Calculation for Volumetric γ-ray Sources Using Geant4 Simulation	2
Analysis of the Effect of Applied Load on Crevice Corrosion Behavior	2
Machine Learning-Based Approach for Hydrogen Economic Evaluation of Small Modular Reactors	2
Quantitative Assessment of Gaseous Effluents during Routine Operation: A Comparative Study of Planned Nuclear Power Plants at Lubiatowo‐Kopalino and Pątnów Sites in Poland	2
Design Change and Operational Consideration of the HVAC System during Nuclear Power Plant Decommissioning	2
Accuracy Evaluation of Monte Carlo Simulation Results Using ENDF/B‐VIII.0 and JENDL‐5 Libraries for 10 MW_th Micro Heat Pipe‐Cooled Reactor	2
Characterization of Waste Generated from Nuclide Management Process in Waste Burden Minimization Technology for Spent Nuclear Fuel	2
High-Temperature Corrosion Behavior of Incoloy 800H Alloy in the Impure Helium Environment	2
Natural Convection Heat Transfer Analysis With Different DHX Operation Conditions of Sodium‐Cooled Fast Reactor Using ATHLET Code	2
CFD‐Assisted Spray Decontamination Process Assessment for Nuclear Tank Decommissioning	2
Methods for Predicting the Minimum Temperature of the Outage Loop and the Maximum Power Caused by the Low-Temperature Coolant	2
A Systematic Framework for Risk Assessment of Fusion Blanket: Addressing Manufacturing Defects, Accident Scenarios, and Radioactive Release	2
Assessing the Impact of Common Cause Failures on Site Risk within Level 1 Multi-Unit PSA	2
Deep Learning–Based Fault Identification Testing Experiment for Bellows Valves	1
A Reduced Order Model Based on ANN-POD Algorithm for Steady-State Neutronics and Thermal-Hydraulics Coupling Problem	1
Transmuting the Arid: Fission‐Powered Visions—Unlocking Ghana’s Aquatic Destiny Through Nuclear Desalination	1
Study on the Dispersion of Radionuclides under Different Hydrological Conditions of Spent Fuel Shipping in Daya Bay	1
Application of EDG AOT Extension Based on the Risk-Informed Method in NPPs	1
Acceptable Level of Acceptance and the Affecting Factors: What Is the Acceptable Public Acceptance of Building a Nuclear Power Plant	1
Experimental Study on Unsteady Radon Exhalation from the Overburden Layer of the Uranium Mill Tailings Pond under Rainfall	1
Alternate Method for Calibration of PRDs by Means of Gamma Radiation Emitted by Radionuclides	1
Effect of Photomultiplier Tube Voltage on the Performance of Sealed NaI (Tl) Scintillator Detectors	1
Pressurized Water Reactor Transient Detection With Artificial Intelligence to Support Reactor Operators	1
Nuclear Power Sustainability Path for China from the Perspective of Operations	1
Numerical Simulation of UF ₄ Erosion Behaviors in Fluorination Furnace	1
Influence of Weak Compressibility on the Hydrodynamic Performance Evaluation of Pump Turbines in the Pump Mode	1
Uranium Recovery from Phosphates for Self-Sufficient Nuclear Power in the Eastern Mediterranean	1